Download Presentation

The IRSN’s Reactor Safety Division and its Contribution to the Reactor Safety Assessment

An Image/Link below is provided (as is) to download presentation

Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author.While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server.

Presentation Transcript

The IRSN’s Reactor Safety Divisionand its Contribution to the Reactor Safety Assessment

Giovanni Bruna - Jean-Luc Chambon (IRSN / DSR)2010 November, 26

Current French Reactor Development Strategy

900 MWe Series

CP0

6 units

900 MWe Series

CP1

18 units

French NPP’s Fleet

1450 MWe Series

N4

4 units

99

98

97

96

95

Chooz BCivaux

94

900 MWe Series

CP2

10 units

1300 MWe Series

P4 & P’4

8 + 12

93

92

91

90

89

CattenomBelleville

Nogent, PenlyGolfech

88

87

86

85

84

PaluelSt AlbanFlamanville

83

St LaurentChinonCruas

82

81

80

79

Tricastin, GravelinesDampierre, Blayais

78

77

76

Bugey

Fessenheim

75

74

73

72

71

1970

Research Reactors and Mock-up Experiment Facilities

Reactors for material irradiation :

OSIRIS (70 MW), RJH (100 MW)

Reactors for fundamental Research :

ORPHEE (14 MW), RHF (58,3 MW)

Reactors dedicated to safety studies :

CABRI (14 MW), PHEBUS (38 MW)

Reactors Physics Mock-ups :

EOLE (10 kW), ISIS (700 kW), MINERVE (100 W), MASURCA (5 kW)

Reactor Safety Demonstration

Radiological targets and protection against radiation

Safety principles

Defence in depth

3 barriers

Safety functions

Design concept

Deterministic analysis

Postulated initiating events

Plant conditions category (PCC) used for design

Risk reduction category (RRC) used to complete the design

Probabilistic analysis

Internal and external hazards analysis

Excluded

Accounted for

DBA ACCIDENTS

PROTECTION

INCIDENTS

CONTROL

OPERATION

BDBA ACCIDENTS

SEVERE ACCIDENTS

MITIGATION

Reactor Safety Demonstration : Defense in Depth

During the whole Plant Life (From Construction to Decommissioning)

RISK

FORBIDDEN

RANGE

Control of nuclear chain- reaction(Reactivity – Criticality)

Fuel and Core-cooling-down (Coolability)

Confinement

of radioactive contaminants

ALLOWED

RANGE

LIKELYHOOD

SAFETY FUNCTIONS

BARRIERS

Reactor Safety Demonstration : Principles

SAFETY APPROACH AND TOOLS

Safety Assessment 1/2

The major aim of the Safety Assessment of Nuclear Power Plants is the evaluation (and when possible, the quantification) of all potential risks, including those originated by either voluntary changes in design and operation (refurbishment, fuel loading) or involuntary ones (ageing, degradation of materials and fuel …).